ML060550283

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Revision to NRC Staff Safety Evaluation for Oyster Creek Individual Plant Examination (IPE)
ML060550283
Person / Time
Site: Oyster Creek
Issue date: 12/07/1994
From: Dromerick A
NRC/NRR/DLPM/LPD1
To: J. J. Barton
GPU Nuclear Corp
Reckley W, NRR, 415-1323
Shared Package
ML060550281 List:
References
NUDOCS 9412120134
Download: ML060550283 (4)


Text

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t NUCLEAR RtGO4OTO'RY J, MSON, 9

0 ~WA SH9OQ. O.

2,.

Mr. John J. Barton Vice President and Director GPU Nuclear Corporation Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, NJ 08731

SUBJECT:

OYSTER CREEK NUCLEAR GENERAriNG

,TN'.INDIVIDUAL PLANT EXAMINATION (IPE) $SUBM ITTAL- (AC. N

,443)L:

Dear P r,

barton:

In a letter dated August 2, 1994, the staff tr $,1 dtted ts Staff Evaluation regarding the Oyster Creek IPE for lnte"nateV4ni2ahd :internal floods. On page 18 of the Staff Evaluation 'it inadiertentli tat.edthat the licensee planned actions regarding:

Increased training on thecjnlpor tc the core,spray system.

Changes to maintenance scheduali n f tcore spray system to improve downtime.

Programs instituted to reduC-e blockag drandf foulIng of the isolation condensers,.

In a letter dated November 8, 1994, 'GP-..Nuclea pcrporation stated that the actions and commitments initially ident fi edA 1n'SettI on 8.1L3.of the:Oyster Creek Nuclear Generating Station (OCNG$)S.IPE b til.,1Report pertained to the containment spray system and astociated;heat'e>xcbge rs; and are not related to the core spray system or, the is olation' andeniserf

.sstated in the NRC Staff Evaluation.

Therefore, the staff has revised pageff18.ofthe tiff. Evaluation In accordance with the actions described in sectio 1 3.PE Submittal Report.

'AleanderoW.r omerick, Sr. Project Manager Pro3jct' Diteo rate 1-4 DW.i o'in of Re:ctor Projects -

I/Il Off ike o::of; Nulear Reactor Regulation

Enclosure:

Revised Page 18 of Staff Evaluation Dated August Z 1994; cc w/encl:

See next page

Mr. John J. Barton Vice President and Director, GPU Nuclear Corporation Oyster Creek Nuclear Generating, Stat-Post Office Box 388 Forked River, NJ 08731

SUBJECT:

OYSTER CREEK NUCLEAR GENERAtING STATWjN INDIVIDUAL PLANT EXAMINATION (PIE) ?SUBMITTAL (TAC NWh 74443)-

Dear Mr.

Barton:

In a letter dated August 2, 1994, thesitaffC trap' mtted itsStaff Evaluation regarding the Oyster Creek IPE for interna eve n Iand lnternal floods. On page 18 of the Staff Evaluation it inAdyertentlytated that the licensee planned actions regarding-Increased training on th elipporta ae 0f the core spray system.

Changes to maintenance'.sc, Jwdu1i f6h 6.-~ore spray system to improve downtime.',

Programs instituted to.redue Abl ock n fouling of the isolation condensers.,.

in a letter dated November 8, 1994, GPU Nuclear.:: orpration.stated that the ractions and commi tments initially ident1fied inSection'8.1.3 of the Oyster Creek Nuclear Generating Station (OLNGS)' I PE-Sub ittal Report pertained to the containnient spray system and associated heat exchangers and are not related to the core spray system or the 1solatIon; at ondensrd sasr stated in the NRC Staff r.vdl atio.

2 of).

Therefore, the staff has revised page.1of

theStf, f Evaluation in accordance with the actions described in sectIon 8.'13.of t 3

CNGS. IPE Submittal Report.

Silncerely

()rip~iln~dt sili~n~dy.:;

Alexander. -W merXk, Sr. Project Manager R - Project -Qlre t ate:.l>4:

D vtsionv ottor'Projects I/Il

-b eactor Regulation fncl osure:

Revi sed Page 18 of Staff-.

Evaluation Dated: August 9

2 19 94 cc w/encl.

See next page P.J.JUR Lt.L0 N;

Docket File OGC OC/LfDCB

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Mr. John J. Barton Vice President and Director

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cc:

.: Oyster CrAek Nuclear

.,Geerating Station Ernest L. Blake, Jr., Esquire -

Shaw, Pittman, Pottsl&-Trowbrld 2300 N Street, NW.

Washington, DC 20037 Regional Administrator, Reglon.t U.S. Nuclear Regulatory Commiis:'i 475 Allendale Road King of Prussia, Pennsylvanfa '1,

- 4.

BWR Licensing Manager.

GPU Nuclear Corporation'.i I Upper Pond Road Parsippany, New Jersey 07054 Mayor I 1.

Lacey Township 818 West Lacey Road Forked River, New.Jersey 08731 pj r, Licensing Manager Oyster Creek Nuclear Generating-Mail Stop:

Site Emergency Bldg..

Post Office Box 388 Forked River, New Jersey:08731 j:

StM~iI Resident Inspector

,, tl-2,,

c/o U.S. Nuclear Resulatory Comn Post Office Box 445

.

I Forked River, New Jersey 08731"'

Kpnt Tosch, Chief New Jersey Department of Environmental Protection Bureau of Nuclear Engineerjng CN 415 Trenton, New Jersey 08625':'

, 11 1 I

7.

eei c Saety-IsIues$

As part of the IPE submitta t, (:en$ 41 onut of several generic issues including USI A-47,mSYoter.hlag t1On In Nuclear Power Plants;" USI A-47, Safety Implicatilo Wf't ol;Sywtems:N Generic Issue (GI)-1O1, "BWR Water Level RedundahCy$.),

L 0i ig System LOCA at BWRs."

However, USI A-o7lvGI~1O1 ndG 6 e resolved by staff with no new requirements. Accordingti:,

lihe ns proPoied resolution of these issues was not reviewed in detal lhhe lf the ltcensee's response to Generic Letter 89-19, 'Request for Acto i

to Resolution of Unresolved Safety Issue A-47,' addresses USA4 r t1. l:

8.

Licensee ActIons and i

Comiitment The licensee used the IPE process to4 deAntify+ iV}ant and/or procedural modifications.

The IPE took crediit. for sever l~

modifcations that the licensee installed during the 14R refuel Itw

e. These Ainclude Installation of a hard piped containment vent System; pperator training for manual Initiation of the containmentiipray syttei and lnstallation of interconnection to the combustion turbine genei~tors at-the adjacent Forked River Site.

The combustion tUrbin 4It6rc0nnh p.1 wi1l make it possible to supply power from the combustion tUrbl IeSd ly to non-essential 4160 V bus IA and emergency loads of essential 41lO....Y:

1 and 1D.ia cross-tle.

Purchasing a portable power generato6rad deetda p1ng procedures for recovering offsite or onsite power were identified.ais ;.dd~ nal 1mprovements for coping with station blackout. While the procedureldt 4

lopment Cis underway, the licensee plans to evaluate the purchgii ng fMiddiYtional :AC generator before the 15R jefueling outage. iThe`stiafff icO Ai hes1ielcensee's intent to address station blackouit events by~ hh' tntert3 cion to the two combustion turbines and recovery of AC power 'pro.dur A.

IPE findings indicate that there'.are

nur4ber, iddit onal low-cost.

mprovements which could enhance overall ruetorsafety These planned actions include:

o Development of an emergency-procedur for Loss of Offsite Power.

O Development of an emergeq1;y procer.O.for Loss of QC Power.

O Increased training on containment spray syste m.

o Changes to maintenance sh!tL duin g f he containment spray system to improve downtime,-

o ModIfications£ tQ mplemeutthe ReadctlO Overfill Protection System.

o Consider the development0iF sPeClfiC; idtnce, training, anO procedures for reactor overfilti.6fi entVs.

O increased emphasis in training on kOperatori actions as defined by the IPE.

o Consideration of alternit8contaihmJlt heat removal capability to maintain minimal NPSH atilrt ofAJdent Management.,

o Alternate water suppy dent Management)

I8 Revsed:D0"'r ADOCK:0500 921 P D;.

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